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NUMBER ,REV LTR/CHG NO.N704-FDR - 990- 004

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~~~~=~.,-----------,----------t DOCUMENT TYPEPROGRAM TITLE F '1" D .. ,DecontaIl1ination and Disposition of Facilities aCl lhes ecommlsslomng ReporProgram' KEY NOUNS

, !i-D~O~C~U~M~E~N~T~T~IT~L~E~--------------------i Fuel De cladding

l-O~R~I-G-IN-A-L-I""SS""U""E"'D"'A""T""'E~----------i

Final Report - SRE Fuel Dec1adding/'

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NAME I~~~~ This report summarizes the task of dec1adding the

W _ F. Heine (10) NB02 ~RE fue~ ~,sem~lies, and sripment of the fuel toA. W. Graves NB02 av~~a f ~~er ,~r e~;.nt~a reprocessing. The dis-G. W. Meyers LAIO posl1hon 0 ~nl entlle RMDF storage canisters,W. R. McCurnin T020 18 a so covere •F. C. Schrag T020E. L. Babcock T020J. P. Page T009V. J. Schaubert(2)NBIOJ. H. Walter T009J. M. Harris T022D. C. Allen NBIOM. E. Remley NB08B. F. Ureda NB02G. P. Streechon NB02W. F. Dennison KB48E. G. Andrews KB45K. E. Buttrey LB34R. J. Tuttle NB13

RESERVED FOR PAOPRIETARY/I.EGAI. NOTICES

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t-....~---------~;:lp;:'* COMPLETE DOCUMENT-:r.)iNO ASTERISK, TITLE PAGE/SUMMARY i I

L-_O_F_C_H_A_N_G_E_P_A_G_E O_N_LY ......a._.....,.,,~~ ,_..."..... __

Document Provided and Located on: http://www.RocketdyneWatch.org

"

.'Atomics Internationa_ NO N704-FDR-990-004

PAGE 1-1- /' .A . _...... ,/ ,- ~ --:: ,.j~

<..- ./ / .. : .~~: .. ;,/ ~:.:•. ' .::..",/ - - /,- '..:..-' /

CONTENTS

Page

. . . .

A-A. Approach •.•••.....•.

A-B. Disposition •...••..•.•

A-C. Accountable Fuel Quantities

A-I

A-I

A-2

A-2

1

1

4

4

6

10

10

10

10

21

22

25

32

33. . .

. . . . .. .

. . . .

.. .

. . .

1. Introduction.

A. History ...

B. Fuel Description

C. Scope of E££ort

II. Compendium

III. Process Description .....

A. Material Receipt .

B. Fuel Element Disassembly

C. Fuel Rod Disassembly

D. Fuel Slug Cleaning •

E. Fuel Slug Packaging

IV. Shipping

V. Records .

VI. Program Supporting Documents

Appendix A Disposition of Contents From 16 UnidentifiedRMDF Storage Canisters ...•

Introduction ..

TABLES

I. List of Dec1ad Fuel Shipment to Savannah River

II. SRE Shipping Container Contents ..•.....

III. SRE Fuel Dec1adding Supporting Documents

26

2934

NOTICE

Tius REPORT IS ILLEGIBLE TO A DEGREETHAT PRECLUDES SATISFACTORY REPRODUCTION

, ;

I I


Atomics Internationa, NO

PAGE

N704-FDR-990-004". ...,1 -~

r----------------- =~.....7':"""'-~:.&l~II'_=_~...=..,~, __.

TABLES

Page

A ..I.

A-II.

A-ill.

Unidentified Storage Container Contents • . . . . • A-3

Fuel Waste From 16 Unidentified Canisters . . ...• A-5

Summary of Current Status •...•..••.•....•..•....• A-6

FIGURES

. . . .

.. . . . .

. . .. . .

1.

2.

3.

4.5.

6.7.8.9.

10.

11.12.

13.

14.

15.

16.

17.

18.

19.20.

SRE Fuel Assembly and Rod Configuration .

SRE Fuel Storage CallS ........•...••.•.....••

Babcock Transfer Cask Being Loaded at the RMDF

Babcock Cask on Dolly at the AIHL ...•...•..

AI Hot Lab Facility Layout .

Work Stations for SRE Repackaging Core I ..

Work Stations for SRE Repackaging Core II .

SRE Fuel Declad ProceSs Flow Chart . • . . .

Fuel Rod Washing Tank In-Cell. . . • . . • . . . . . . . ...•.

Chuck and Tubing Cutter, and Fuel Slug Remover ....•.

Cutting Chisel Tool U sed to Remove Damaged Cladding .

Fuel Slug Washing Tray .

Dowanol Disposal System - Core I

Dowano1 Disposal System - Core II .....

NaK Distallation System . . . . . . . . • . • ..••

Final Closure Weld System for Shipping Canisters •..

Weld Leak Check Water Tank .•....••.•..•.•.

TREAT Loop Cask Loaded for Truck Shipment ••.

Babcock Cask Loaded for Truck Shipment ....

SRE Fuel Shipment Enroute to Savannah River

I I

2

3

11

11

12

13

14

15

17

1718

1920

20

23

23

24

27

27

28


Atomics International

A. HISTORY

NO

PAGE

I. INTRODUCTION

N704-FDR-990-004

1

Atomics International is engaged in the dismantling and disposal

of the Sodiunl Reactor Experiment (SRE) as part of a broader decontam.i

nation and disposition program originally funded by ERDA through the

Division of Waste Management and Transportation, and later by the Division

of Environm.ental Controls Technology. This report sum.m.arized that part

of the program which prepared the irradiated SRE fuel for shipment to and

eventual recovery in the ERDA owned Savannah River Plant, Aiken, South

Carolina, which is presently operated by E. I. duPont de Nemours & Co.

A schematic of one of the fuel assemblies is shown in Figure 1.

The remaining irradiated SRE fuel had been stored in the irradiated

fuel storage vault at the Radioactive Materials Disposal Facility (RMDF)

since its removal from the SRE reactor. Core I was removed in 1959

after an incident which resulted in the overheating and failure of one or

more fuel rods in a nmnber of fuel assemblies. The 26 undamaged fuel

assemblies were shipped to Oak Ridge National Laboratory and were re

processed. The assemblies having damaged rods, along with miscellaneous

fuel pieces which were retrieved fro m the reactor, were repackaged into

stainless steel canisters and stored in the RMDF. This damaged Core I

fuel was estimated to contain about 1300 kg of uranimn, including 35 kg of

U235

• The Core II fuel assemblies were removed from the reactor in

1964 and stored in the RMDF. This fuel, including some low enrichment

experimental fuel, was estimated to contain about 227 kg of uranium., in

cluding some 148 kg of U235 • The total fuel recovered was 1686 kg of

uranium metal, 190 kg U235 , and 608 grams of Pu239.

Upon removal from the SRE reactor, the Core I fuel was placed in

34 stainless steel canisters, 3-1/2 in. in diameter by 120 in. long.

During GFY 1972, the fuel canisters were examined, and limited


Atomics Internationat NO 1'1704-FDR-990-004

PAGE. 2

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Figure 1. SRE Fuel Assembly and Rod ConfigurationsDocument Provided and Located on: http://www.RocketdyneWatch.org

Atomics International NO

PAGE

J.~704-FDR-990-004

.3

repackaging was performed, which reduced the number of canisters to

26•. The Core II fuel assemblies, along with some experimental fuel

assemblies, were stored in 68 carbon steel canisters of the same size

as us ed for Core I, as depicted in Figure 2.

B. FUEL DESCRIPTION

The Core I fuel was unalloyed uranium metal, with a nominal 2.8%

U235 enrichznent (as fabricated), clad with Type 304 stainless steel, and

NaK bonded. Core II contained a thorium - 7.6% uranium alloy, enriched

to 92.3% U235 , and was also clad in Type 304 stainless steel and NaK

bonded. In addition, several miscellaneous SRE experimental elements

consisting of thorium - 5.4% uranium alloy, U02, U-Mo, and U-carbide

were in storage at the RMDF.

The Core I fuel assemblies nominally consisted of 7-rod elem.ents

and Core II of 5-rod elements with each rod containing 12 fuel slugs.

Each slug was 3/4-in. diameter by 6 in. long, making an active fuel

column length of 6 it. Wire wrap was used to space the rods within an

assembly. The 6 experimental assemblies contained miscellaneous fuel

slug sizes~

C. SCOPE OF EFFORT

The scope of effort for the SRE fuel decladding task was to place the

fuel in an acceptable condition for reprocessing by means of acid or

electrolytic dissolution at the Savannah River reprocessing plant. As

stated previously, the fuel slugs were thermally bonded to the cladding

with NaK. The presence of NaK represents a hazardous condition for

the dissolution processes. As a result, the eventual reprocessing of

this fuel required special head-end treatment involving the NaK removal.

Inasmuch as the Division of Production does not have this special head

end capability, the processing was, therefore, performed at the AI Hot

Laboratory.


Atomics International NO N704...FDR-990-004

PAGE 4

Cap ------1 --r3"

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Atomics International NO _~704-FDR-990-004

PAGE 5

The major tasks comprising this effort consisted of:

1) On-site transfer of the fuel assemblies from the RMDF to the

AI Hot Laboratory

2) Disas sembly of the fuel elements

3) De cladding of the fuel rods

4) Removal of the NaK from the fuel slugs

5) Repackaging of the fuel slugs and weighing of the loaded

shipping canisters

6) On-site transfer of the fuel from the Hot Laboratory to the

RMDF for subsequent shipment

7) Planning, tooling, and proce ss development for the above


Atomics International NO . N704-FDR-990-004

PAGE. 6

II. COMPENDIUM

The SRE fuel decladding task began in July 1974 (FY 1975). The

first tasks accomplished were the selection of the TREAT Loop Cask.

for off-site shipping, identification of the in-cell processes, preparation

of the process safety study (Nuclear Safety Analysis), design of an alumi

num. shipping canister, and preparation of a criticality stu.dy for the

decladding processes and the shipping canister. Following development

of this initial information, the tooling requirements were established,

the in-cell tooling layouts were made, and the tooling design, fabrication,

and assembly were accom.plished•

. The disassembly tooling consisted of remote, in-cell devices for

opening the storage containers, disassembling the fuel assemblies to

separate the fuel rods, reInoving the wire wrap froIn the cladding, cutting

the clad fuel rods to a convenient handling length, melting and removing

the bulk NaK from the rod segments, and pushing the intact fuel slugs out

of the cladding. The damaged fuel required the development of additional

tools to manually strip the cladding from the fuel.

The tooling for NaK rem.oval consisted of alcohol washing tanks,

manual scrub brushes, ultrasonic alcohol cleaning tanks, and a NaK

vacuum distillation furnace for residual NaK removal. The damaged

fuel required the development of a hot alcohol bath process to remove

the NaK from the porous surface, after extensive testing of the NaK dis

tillation process proved impractical.

A weighing system, designed and fabricated by an outside con

tractor, was used to tare weigh the shipping canisters and spacers,

and to weigh the seal-welded canister containing the declad fuel. The net

weight was used for accountability. An in-cell welding system was devel

oped for performing the shipping canister seal weld after the fuel had

been loaded. The welder was programmed for automatic operation,


Atomics International NO J.'l704-FDR-990-004

PAGE 7

using parameters developed and qualified in an out-of-cell test program.

Weld repair parameters were also developed and qualified for in cell use.

A leak test tank was also developed for use in the final quality assurance

test of the integrity of the welded shipping canister.

Concurrent with the tooling preparation efforts, the Nuclear Material

Management Plan and the Quality Assurance Functional Plan were devel

oped. Test Plans were written for the NaK distillation and for the ship

ping canister weld development, and the testing was performed accordingly.

Early in the decladding program, the safeguards requirements of

10 CFR 73 for the licensed AIEL facility, and AECM-2405 for the ERDA

owned RMDF facility were reviewed for application to the SRE Core II

fuel. This fuel contained uranium enriched to 93 percent U235 . The

basic requirements of the se documents stated that fuel enriched to

greater than 20 percent U235 , when present in quantities of greater than

5 kg of U235 must be provided physical protection. Exemptions to these

safeguards requirements were requested on the basis of the radiation

levels of 50 R/hr at 3 ft associated with the irradiated Core II fuel. The

requests were denied due to the fact that such exemption requires that

associated radiation levels be greater than 100 Rlh at 3-ft distance. The

AI Security Plan was therefore revised to include the decladding operations

of the AIHL, and submitted to the NRC for approval. The AIHL was subse

quently m.odified to incorporate the full safeguards requirements of 10 CFR 73,

and the RMDF was m.odified per ERDA/SAN direction, to provide equivalent

protection to AECM-2405 for the Core II fuel.

Since the AIEL required physical protection modifications before

Core II could be declad, the program sequence was modified to begin the

operations on the Core I fuel. Originally the Core II fuel was to have


Atomics International NO ..,I04-FDR-990-004

PAGE 8

been declad first, as it was known to be intact and easier to clean. The

experience on the Core II fuel would then have been useful to the more

complex operations on the damaged Core I fuel.

Fuel decladding checkout operations began on the Core I fuel in May

1975, and full scale operations began in July 1975. The first year of

SRE fuel decladding effort (FY 1975) culminated in completing all prepa

rations necessary to begin full scale operations on the intact SRE fuel.

The only development still in progress at the start of the second year

(FY 1976) was the NaK cleaning for the damaged fuel.

The extent of the damage to the Core I fuel involved in the 1959 fuel

cladding melting incident was difficult to estimate priQr to beginning the

actual decladding efforts. Once operations began, it became obvious that

the cladding removal process was inadequate in the case of the damaged

fuel, the NaK removal process was not effective on the damaged material,

and there was more damaged fuel than anticipated. The cladding had to

be mechanically peeled from the fuel slugs due to a metallurgical bond

which had formed, thus requiring the development of additional tools.

The NaK had to be reacted from the pores of the damaged slugs using

hot alcohol, as the total fuel surface area was too great to effectively

distill the NaK in a vacuum. distillation furnace which was initially tried.

Additionally, the alcohol us ed in the initial wash was trapped in the pores

and created a seemingly endless off-gasing in the vacuum furnace. This

required the development of a hot alcohol bath process in an autoclave.

Unfortunately, the requirements for the development of the hot alcohol

bath developed after extensive time had already been spent on developing

the NaK distillation. This added scope was reflected in the requirement

for added mid-year funding to meet the forecast completion schedule for

the Core I dec1adding.

In August 1975, 16 containers of fuel that were no longer being car

ried on the RMDF inventory were located in the facility vaults. A


Atomics International NO 1'1704- FDR- 990-004

PAGE 9

complete inventory of the vaults verified the absence of any additional fuel

not listed in the RMDF records. A search of the accountability records

revealed that most of the fuel in the 16 containers had been listed as

previously disposed. A detailed accounting of the problem of the 16

containers is provided in Appendix A.

The Core I fuel, experimental fue1,/~and the 16 containers of low

enriclunent fuel was all processed and repackaged by December 1975.

Cell cleanup was performed upon completion of the processing of the low

enriclunent fuel. Core II fuel processing was begun in January 1976,

following revision of the Nuclear Safety Analysis and following NRC

approval of the Safeguards and Security Plan.

The Core II decladding operations were completed in June 1976, and

final cell cleanup was begun. The Appendix A submittals, required by

Savannah River, were approyed in June. The second year of the dec1adding

effort (FY 1976) culminated in the completion of all SRE fuel processing

operations and the return of all repackaged fuel to the RMDF for ship

ment to Savannah River.

The transition quarter (FY 1976 T) saw the initiation and completion

of the Core I and experimental fuel shipments to Savannah River in the

TREAT Cask. Also, initiation of final cell cleanup, disposal of the fuel

waste from the 16 containers, and preparation of the loading specifica

tion for the ERDA escorted Core II fuel shipments to Savannah River were

accomplished. In FY 1977, cell cleanup was completed and Core II ship

ments to Savannah River were completed by ERDA escorted couriers.


Atomics International NO "1104-FDR-990-004

PAGE 10

m. PROCESS DESCRIPTION

A. MATERIAL RECEIPT

The fuel material was received at the AI Hot Laboratory (AIEL) in a

specially designed shielded. transfer cask, known as the Babcock Cask, which

is shown in Figures 3 and 4. The fuel container was removed from the cask

directly into Cell 4 in the AIHL. The container was immediately transferred

to a storage rack, which was designed for storage of three containers. As

these cans were removed from the storage rack to be placed in work, ad

ditional fuel cans were received and moved to this storage rack to provide

a continuous supply of input material to the disassembly station. Figure 5

is a facility layout of the AIHL. Figures 6 and 7 are expansions of the

AniL layout and shows the locations of the process steps for Cores I and

II. Figure 8 depicts the material flow through the entire decladding and

packaging operation.

B. FUEL ELEMENT DISASSEMBLY

At the disassembly station, the fuel was removed from the fuel can.

Fuel rods were disassembled from element form by removing the holding

cotter keys and lock wires. During the disassembly process, fuel serial

num.bers were verified to reconcile records. Discrepancies were resolved

by the AIEL and the Nuclear Material Management Managers, before

further disassembly of the discrepant items was initiated. The fuel rods

were then transferred to a washing tank (Figure 9) containing Dowanol to

remove any residual external Na or NaK. After washing, the fuel rods

were transferred to the rod disassembly rack.

c. FUEL ROD DISASSEMBLY

The end plugs of the fuel rods were removed by making cuts with a

tubing cutter. The rods were subsequently s~ctioned into approximately

18-in. long sections, also by use of the tubing cutter. The cutting station

is shown in Figure 10. The fuel slugs were removed from the cladding



PAGE

N704-FDR-990-004

11

7704-62508

Figure 3. Babcock Transfer CaskBeing Loaded at the RMDF

7704-62502

Figure 4. Babcock Cask on Dolly at the AIHL

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Atomics International NO J...£704-FDR-990-004

PAGE 16

by holding the fueled section in a vertical position and pushing out the

fuel slugs from the bottom up. The fixture for holding and pushing out

the fuel slugs is also shown in Figure 10. Upon examination of the

damaged Core I fuel in-cell, and attempts to remove the fuel slugs, it

became obvious that additional tools' and procedures were requirea. It

was found that the cladding had to be mechanically cut and peeled from

the fuel slugs due to a metallurgical bond which had formed between the

two. One of the tools, used for chisel cutting the cladding, is shown in

Figure 11.

After rod disassembly, the cladding and fuel slugs were washed in

Dowano1 to remove the NaK. The washing station is shown in Figure 12.

The fuel slugs were allowed to soak in the Dowanol until there was no

longer a visible reaction. The slugs were stored within the cell in the

"dirty" batch store area until they could be transferred to the next oper

ation in Cell No.2.

Fuel element cladding from the removal operation, along with the

wire-wrap wire and other hardware, were packaged in 10-gal. pails and

eventually disposed of as high level waste. The cladding was visually

checked during removal and/or before disposal to assure that any en

trapped pieces of fuel had been removed.

The dirty Dowano1 was poured from the washing tanks through a

wire screen into a weir box trap. The contents of the weir box were

pumped to a 55-gal. drum located in the adjacent decontamination room

behind the cell for holdup. The liquid was later solidified for disposal

a s solid waste. A diagram of the Dowanol disposal systems are shown

in Figures 13 and 14. Any pieces of fuel that were collected on the Wire

-screen were placed in a previ.ously tare weighed waste can which was

identified and designated for that purpose. Any material collected in this

system eventually was placed with identical material in the final shipping

canisters.


Atomics International NO N704-FDR-990-004

PAGE 17

9070-6276

Figure 9. Fuel Rod Washing Tank In-Cell

7704-4412

Figure 10. Chuck and Tubing Cutter,and Fuel Slug Remover

Reproduced frombest available copy.Document Provided and Located on:


-g z» 0G'lm

I:T''''(D (D-

"'-0-...o010.< c:~~Qlo.I:T'G::;"

o33~ Figure 11. Cutting Chisel Tool U sed to Remove Damaged Cladding

9070-6281

t-'ex>

~o3a·:JS"

ici"i1

•.e.......:]ooJ>.Ih:Jtl~I

...0

...0oIoooJ>.



PAGE

N704-FDR-990-004

19 Reproduced frombest available copy.

.N.-l


Atomics International NO •• 104-FDR-990-004

PAGE 20

tJECtJtV 3= CCC!.. 3

55 GAc.CRt/it?

STAND PIPE '.",,:. •.. ,r-0",'-_~Qi!:.0!J.C.!"Lt.-WINOOW

S GAt.SUMP...

• I ~---_t:==UC"""""'-- -rrJ • .~.

~;. • ,.-. . "& ;.'. .:,.\P,.C't." __ ...

--_.---~-=._----_.._--- --.......-.-----Figure 13. Dowana1 Disposal System - Core 1

O£CON~ CELL .3

~6AL SUMP

SCREEN\ ...

05<:;,41. 5UI'/!,o

IAI DRAIN:"\ .,o05/T/ON

t:~-n1>OV rvB/AJ5 ........~-5M-L-~-W~-=~~~§§~5\ [.",,\, .. / . </""

(F - - I ,-r:-----------1~~~. '" ,::r::J 6ALD/?UM

Figure 14. Dowanol Disposal System - Core n


Atomics International NO ...,,704-FDR..990 ..004

PAGE 21

The empty cans which contained the incoriting fuel assemblies were

disposed of as low level waste.

D. FUEL SLUG CLEANING

The IIdirtyll fuel slugs were received into this operation from the

IIdirty" fuel slug storage area. The slugs were removed from the con

tainer and placed into the slug washing tank where they were cleaned in

alcohol. Stubborn deposits of bonding material were removed by brushing

the fuel slug with a nylon brush. The slugs were then placed in an

ultrasonic tank for a final alcohol cleaning. Previous studies and sub ..

sequent operations conducted by Atomics International demonstrated that

alcohol has no discernible reaction with uranium or uranium alloys.

To assure that all residual NaK had been removed, the batches of

fuel slugs which were suspect of exhibiting NaK after the previous

cleaning steps were processed through an additional cleaning step which

consisted of a NaK distillation or a hot alcohol bath. The initial NaK

cleaning process was NaK distillation. However, it was found that this

method was impractical for use on the damaged fuel slugs taken from

the overheated fuel elements. These slugs exhibited cracks and pockets

which contained NaK in quantities too large to be handled by the dis ..

tillation teclmique. More detail is provided in N704-ER-990-002,

"Selection of NaK Removal Process for SRE Fuel,1I dated October 2,

1975.

For the NaK distillation, a basket of fuel slugs was loaded into a

retort and the retort placed in a furnace. The distillation parameters

were: (1) Vacuum - 50 microns or better, (2) Temperature - 7500-

8500 F, and (3) Time - 1 hr. A cold trap was located between the retort

and the vacuum pump to condense the NaK vapor. The cold traps were

periodically removed to react any NaK which had been collected. After

the distillation cycle, the fuel slugs were considered NaK free when there

was no NaK visible on the cold trap. The slugs were then transferred



PAGE 22

to a clean in-cell transfer container and were moved to the "clean" batch

storage area in the adjacent Cell No.4. The NaK distillation system is

shown in Figure 15.

For the hot alcohol bath process, six racks, each containing six fuel

slugs were loaded into an autoclave containing 4-1/2 gal. 0:£ ethyl alcohol

and 8.6 ounces of acetic acid. A condenser was provided to keep a liquid

cover on the fuel at all times. The alcohol was heated and maintained at

140°F. The hydrogen gas that evolved was vented through a liquid bubbler.

The fuel slugs were considered NaKfree in 20 hours, or when no more bubbles

were seen in the bubbler during a 6 -min. interval, whichever occurred.

first. The fuel racks were transferred to a clean in-cell transfer con

tainer, and were moved to the Ilclean" batch storage area in Cell No.4.

The dirty Dowanol and alcohol were dumped into the radioactive liquid

waste system in Cell No.3. The alcohol was first poured through a wire

mesh screen to collect any pieces of fuel which remained in the ultra

sonic tanks. The contaminated nylon brushes were visually checked for

fuel pieces before being disposed of as waste.

E. FUEL SLUG PACKAGING

The fuel slugs from the ltcleanll batch storage area were transferred

into a shipping canister. Two canisters were used - EX-N704000025,

Rev. A, SRE-Savannah River Core I Shipping Can, and EX-N704000065 N!C,

SRE-Savannah River Core IT Shipping Can. The canisters contained spacer

tubes of the appropriate diameter of fuel slugs. The slugs were loaded

into the spacer tubes until the tubes were filled to capacity. The lid was

placed on the canister and the unit moved directly to the, weld station

where the final closure weld was made. The lid was welded to the canister

using tungsten inert gas welding. Thewelding statiOn is shown in Figure 16.

The welding development and resultant parameters are described in

N704-TR-990-001 N!C, IIClosure Weld Development Test Report, SRE

Fuel Decladding," dated September 2, 1975. The welded canister was then


Atomics International NO 1~ 704-FDR-990-004

PAGE 23

7704-4017

Figure 15. NaK Distillation System

7704-4014

Figure 16. Final Closure Weld System for Shipping Canisters

Reproduced frombest available copy_


Atomics International~ ....,.

NO

PAGE

.704-FDR-990 -004

24

weighed to :1:0.0 lIb u$ing a. load cell. The previously determined tare

weights of the canister, lid,and spacer tubes were subtracted from the

total weight, with the difference being the amount of fuel contained in

the loaded canister.

After the welding and weighing operations were completed, the

shipping canister was moved to the leak check water tank. The tank is

shown in Figure 17. The canister was immersed in the water which was

approximately 1500 F. The elevated temperature pressurized the gas

sealed in the canister, and the canister was visually observed to deter

mine if a leak existed as manifested in the form of bubbles. The container

was then allowed to dry and then moved to the "loaded storage canister"

rack for subsequent transfer to the RMDF.

7704-4012

Figure 17. Weld Leak Check Water Tank Reproduced frombest available copy.


Atomics International

IV. SHIPPING

NO

PAGE

N'704-FDR-990-004

25

Shipznents of the dec1ad fuel to Savannah River were znade in the

TREAT Loop Cask. Four shipping canisters, contained in the cask,

coznprised a shipznent. The Core I and experiznental fuel were trans

ported by coznznon carrier truck (Tri State Motor Transit Co.) in five

shipznents. The Core II fuel, due to enrichznent, required znoveznent

by governznent (ERDA) truck in nine shipznents. The fourteen total

shipznents are sUInznarized in Table I. The TREAT Loop Cask, loaded

for shipznent, is shown in Figure 18. The Babcock Cask, which was

also required for transfer of the fuel frozn the TREAT Cask at Savannah

River, accoznpanied each fuel shipznent, and is shown in Figure 19.

Figure 20 shows a Tri State shipznent in progress.

The requirements and procedures for loading and shipping the SRE

dec1ad fuel are contained in N704-ACR-990-009 N/C, N704-DWP-990-0l3

N/C, and NK396-00002, Rev.A.

A sUInInary of the contents of each shipping canister is presented in

Table II.



PAGE 26

TABLE I

LIST OF DECLAD FUEL SHIPMENT TO SAVANNAH RIVER

Shipment No. Canister Nuxnbers Fuel Type Date ShippedCurie

Content

1 AI-1O, 11, i6, 19 Core I 8-9-76 1612

2 AI-4, 8, 12, 17 Core I 8-20-76 1861& Exp. I

3 AI-5, 6, 7, 9 Core I 8-31-76 1914

4 AI-I, 2, 3, 15 Core I 9-11-76 1705& Exp.

5 AI-13, 14, 18, 53 Core I 9-20-76 828& Exp.

6 AI-20, 21, 22, 29 Core II 10-30-76 4018

7 AI-23, 25, 26, 27 Core II 11-8-76 4010

8 AI-24, 28, 45, 46 Core II 11-19-76 4034

9 AI-36, 47, 51, 52 Core II 12-2-76 3723

10 AI-33, 34, 35, 38 Core II 12-12-76 4051

11 AI-3D, 31, 32, 37 Core II 1-7-77 4051

12 AI-39, 40, 41, 42 Core II 1-22-77 4051

13 AI-43, 44, 48, 49 Core II 2-4-77 4043

14 AI-50, 54, 55, 56 Core II 2-19-77 3079

-Document Provided and Located on: http://www.RocketdyneWatch.org

Atomics International NO J.~704-FDR-990-004

PAGE 27

7704-62572

Figure 19. Babcock Cask Loaded for Truck Shipm.ent-.=====~=~"'iii

Reproduced frombest available copy.


Atomics Internationa. NO . N704-FDR-990-004

PAGE. 28

7704-62574

Figure 20. SRE Fuel Shipment Enroute to Savannah River

~eproduced fromest available copy.


TABLE II

SRE 5HIPPING CONTAINER CONTENTS(Sheet 1 of 3)

PieceU

235Shipping Count Net Avg

U Avg Avg PuAvg Th Original Fuel AssemblyCanister 6-ln. Weight Weight Weight Weight Weight Remarks

No. Slugs (gm) 0/. U (gm) %U235 (gm) %Pu (gm) % Th (gm) Identity Number

(equiv.)

AI-OI 119 98,041.10 99.89 97,933.15 2.696 2,640.28 0.039 38.24 - - 5U-I-42, -45 Unalloyed Uranium MetalAI-02 115 98,884.05 99.89 94,779.68 2.696 2,555.26 0.039 37.01 - - SU-I-42, -16 Unalloyed Uranium Metal

AI-03 114 93,441.60 99.89 93,338.81 2.696 2,516.41 0.039 36.44 - - 5U-I-42, - 39, -7 Unalloyed Uranium Metal

AI-04 112 92,321.20 99.89 92,219.65 2.696 2,486.24 0.039 36.01 - - SU-I-13, -7 Unalloyed Uranium Metal

AI-OS 116 95,591.66 99.89 95,486.51 2.696 2,574.32 0.039 37.28 - - SU-I-13, 5U-23-4,.5 Unalloyed Uranium Metal

AI-06 110 92,942 .64 99.89 92,840.40 2.696 2,502.98 0.039 36.25 - - 5U-I-3, -7, STJ-23-5 Unalloyed Uranium Metal

AI-07 (108) 89,245.80 99.89 89,147.63 2.696 2,403.42 0.039 34.81 - - 5U-I-47, -17, -32, 5U-I-9, Unalloyed Uranium Metal-31,-12 (50me fragments)

AI-08 . 112 92,121.62 99.89 92,020.29 2.696 2,480.87 0.039 35.93 - - SU-I-25, -38, -3, SU-23-5, Unalloyed Uranium Metal71520-035

AI-09 117 93,060.58 99.89 92,958.21 2.696 2,506.15 0.039 36.29 - - SU-I-3, -40, 71520-035 Unalloyed Uranium M<>tal

AI-IO (74) 58,995.22 99.89 58,930.33 2.696 1,588.76 0.039 23.01 - - SU-I-15, 7i520-035 Unalloyed Uranium Metal(Some fragments)

AI-II (106) 87,386.04 99.89 87,289.92 2.696 2,353.34 0.039 34.08 - - 5U-I-47, -31, -12, -16 Unalloyed Uranium Metal(Some fragments)

AI-12 18 + 15 83,879.71 99.89 83,787.44 2.696 2,258.91 0.039 32.71 - - SU-3-I, 18 Hollow Cylinder Unalloyed U-Metal-18-4 in. Cyls,+ Mise + Mise 15 slugs, Mise Pieces

AI-13 (60) 26,018.50 89.55 23,299.57 5.978 1,392.58 0.072 18.73 - - 5U-9-3 Uranium-l0% Molybdenum Alloy(Some fragments)

AI-14 Pellets 22,947.62 88.04 20,203.08 7.74 1,563.72 0.039 8.95 - - 5U-7-1 Uranium Oxide-with 55 claddingintact

AI-IS Mise Pos 44,920.00 95.11 42,7Z~.41 9.80 4,186.89 0.035 15.57 - - 5U-20-X, 5U-20-X Uranium Carbide-with 55 claddingintact

AI-16 118 93,491.49 99.89 93,388.65 2.696 2,517.76 0.039 36.46 - - 5U-12-I, 71520-035 Unalloyed Uranium Metal

AI-17 112 92,049.04 99.89 91,947.79 2.696 2,487.91 0.039 35.90 - - SU-I-20, 5U-I-38 Unalloyed Uranium Metal

AI-18 (99) 89,359.20 99.47 88,885.60 2.696 2,396.36 0.039 34.85 - - 77 U-Metal slugs, 22 equiv Unalloyed U-Metai 8< U-Mo AlloyU-Mo slugs (1.2, 1.88< 3.0% Mo)

AI-19 18 + Mise 74,281.53 96.67 71,807.96 2.696 1,935.94 0.039 28.97 - - 5U-3-2, 18 Hollow Cyls + Unalloyed U-Metal-18-4in. eyls.,Mise 3-2 in. acid bath sI ugs, 1-6 In.

fire slug, 2- 30 in. tube fines

AI-20 119 60,941.16 7.43 4,527.93 92.625 4,193.99 Negl. - 92.355 56,282.21 5U-22-03, SU-22-08 Thorium - 7.6% Uranium Alloy

AI-21 119 60,809.62 7.476 4,546.13 92.722 4,215.26 Negl. , 92.375 56,172.89 SU-22-04, SU-22-06 Thorium - 7.6'1. Uranium Alloy

AI-22 119 61,172.50 7.454 4,559.80 92,684 4,226.21 NegI. - 92.365 56,501.98 5U -22-07, SU-22-02 Thorium - 7.6% Uranium Alloy

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TABLE II

SRE SHIPPING CONTAINER CONTENTS(Sheet 2 of 3)

PieceU

235Shipping Count Net Avg

U AvgAvg

PuAvg Th

Original Fuel AssemblyCanister 6-in. Weight%U

Weight% u2 35 Weight

%Pu Weight"/0 Th Weight Identity Nu:mber Remarks

No. 51ugs (gm) (gm). (gm) (gm) (gm)(equiv.)

AI-23 119 61,104.46 1.418 4,569.39 92.818 4,241.22 NegL - 92.312 56,443.41 5U-22-05,-06,-02,-08,-11 Thorium -7.6% Uranium AlloyAI-24 119 61,000.12 7.275 4,437.16 92.139 4,088.91 Neg!. - 92.330 56,321.41 SU-22-10, -09, -II Thorium -7 .6% Urani"m AlloyAI-25 119 61,666.92 7.4996 4,624.17 92.802 4,291.88 Negl. - 92.376 56,961.74 5U-22-09, -01, -12 Thorium-7.6 % Uranium .... loyAI-26 119 60,845.90 7.3195 4,453.62 92.217 4,106.99 Neg!. - 92.335 56,182.06 SU-22-13, -01, -12, -14 Thorium-7.6% Uranium AlloyAI-21 119 61,163.42 7.351 4,496.12 92.333 4,151.40 Negl. - 92.336 56,475.86 SU-n-15, -14, -16 Thorium-7.6% Urani"m AlloyAI-28 119 61,657.85 7.299 4,500.91 92.222 4,150.37 Negl. - 92.33 56,928.69 SU-n-17, -16, -18 Thorium-7.6,." Uranium AlloyAI-29 119 61,139.50 7,341 4,532.30 92.360 4,186.03 Negl. - 92.327 51,002.23 5U-22-19, -18, -20 Thorium-7.1>% Uranium AlloyAI-30 119 61,730,42 1.422 4,581.63 92.608 4,242.96 Negl. - 92.349 57,001,43 5U-n-2 1, -20, -22 Thorium-7,6% Uranium AlloyAI-31 119 61,611.02 7,33 4,516.53 92.365 4,111.69 Negl. - 92.33 56,890.99 SU-22-23, -22 Thorium-7.6'70 Uranium AlloyAI-32 119 I> 1,635.17 1.491 4,617.09 92.817 4,285.44 NegJ. - 92.365 56,929.32 SU-22-26, -25 Thorium-7.6% Uranium AlloyAI-33 119 61,630.63 1.38 4,548,34 92.432 4,204.12 Neg!. - 92.35 56,915.89 SU-22-28, -27 Thorium-7.6% Uranium AlloyAI-34 119 61,612.49 1.364 4,537.14 92.332 4,189.23 Negl. - 92.34 56,892.97 5U-22-29, -30 Thorium-7.6% Uranium AlloyAI- 35 119 61,630.63 7.35 4,529.85 92.402 4,185.67 Neg!. - 92.33 56,903.56 SU-22-31, -32 Thorium-7,6% Uranium AlloyAI-36 119 61,603.42 7.461 4,596.23 92.839 4,261.09 Neg!. - 92.35 56,890.76 5U-22- 33, - 35 Thorium-7,6% Uranium AlloyAI-37 119 61,585.27 7.327 4,512,04 92.227 4,161.32 Neg!. - 92.335 56,864,76 SU-22-34, -35, -36, -3D, Thorium - 7.6% Uranium Alloy

- 32, -25, -27AI-38 119 61,594.34 7.34 4,521.02 92.34 4,174.71 Neg!. - n.33 56,870,05 SU-22-36, -31, -38 Thorium '-7.6% Uranium AlloyAI-39 119 61,621.56 7.29 4,492.21 92.24 4,143,61 Negl. - 92.32 56,889,02 5U-22-38, -39, -40 Thorium-7,6% Uranium AlloyAI-40 119 61,571.66 1.50 4,617.. 87 92.86 4,288.15 Neg!. - 92.37 56,813,74 SU-22-40,-41,-42 Thorium-7.6% Uranium Alloy

. AI-41 119 61,598,88 7.36 4,533.68 92.426 4,190.30 Neg!. - 92.34 56,880.41 5U-22-42, -43, -44 Thorium~7.6%Uranium AlloyAI-42 119 61,626.10 7.39 4,554.17 92.49 4,212.15 Negl. - 92.41 56,948,68 SU-22-44,-45,-46 Thorium-7,6% Uranium Alloy

AI-43 119 61,598.88 7.37 4,539.84 92.40 4,194.81 Neg!. - 92.36 56,892,73 SU-22-46, -47, -48 Thorium-7.6% UraniLlm AlloyAI-44 119 61,571.66 7.41 4,562.46 92.59 4,224.38 Negl. - 92.35 56,861.43 5U-22-48,-49,-50 Thorium-7.6% Uranium AlloyAI-45 119 61,611.46 7.36 4,539.02 92.441 4,195.92 Neg!. - 92.34 56,947,43 SU-22-50, -51, -52 Thorium-7,6% Uranium AlloyAI-46 119 61,558.06 1.37 4,536.83 92.41 4,192.48 Neg!. - 92.33 56,836.56 SU-22-52, -53, -55 Thorium -7.6% Uranium AlloyAI-47 119 61,544.45 7.41 4,560.44 92.57 4,221.60 Negl. - 92.34 56,830.15 5U-22-54, -55, 5U-23-01 Thorium-1.6% Uranium AlloyAI-48 119 61,648.78 7.51 4,629.82 92.896 4,300.92 Negl. - 92.38 56,9 5 1.14 SU-22-56, 5U-23-01, -02 Thorium-7.6% Uranium AlloyAI-49 119 61,412.90 7.46 4,581.40 92.751 4,249.29 Negl. - 92.31 56,727.10 5U-22-56, -57, -99 Thorium-7,6'7. Uranium AlloyAI· 50 119 60,673.54 5.40 3,216.37 93.13 3,051.28 Negl. 0 H.60 51,391.17 5U-2-02, 5U-25-0I, Tho rium - 5.4% Uranium Alloy

Can U-12

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TABLE II

SRE SHIPPING CONTAINER CONTENTSSheet 3 of 3)

PieceUZ35

Shipping Count Net AvgU Avg

Avg Pu Avg Th Original Fuel AssemblyCanister 6-in. Weight %U Weight % U235 Weight % Pu Weight 0/. Th Weight Identity Number RemarksNo. Slugs (gm) (gm) (gm) (gm) (gm)

(equiv.)

AI-51 119 61,521.77 7.526 4,630.38 93.403 4,324.90 Neg!. - 92.391 56,840.69 - Thorium -7.6% Uranium Alloy

AI-52 81 41,903.57 7.58 3,176.29 93.048 2,955.47 Neg!. - 92.40 38,718.90 - Thorium-7.6% Uranium Alloy

AI-53 (36) 28,241.14 97.88 27,642.43 2.767 764.87 0.039 10.78 - - - Uranium-Molybdenum Alloy(1.2, 1.8 & 3.0% Mo)

AI-54 82 42,352.63 7.41 3,138.33 92.56 2,904.84 - - 92.34 39,108.42 - Thorium -7.6% Uranium Alloy

AI-55 81 40,565.45 5.35 2,170.25 92.82 2,014.43 - - 94.46 38,318.31 . Thorium - 5.4% Uranium Alloy

AI-56 79 40,737.82 5.32 2,167.25 92.857 2,012.44 - . 94.56 38,521.63 - Thorium- 5.4% Uranium Alloy

TOTALS 3,679,139.75 1,685,545.72 189,524.43 608.27 1,972,017.77..

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Atomics Internationa~ NO ..~704-FDR-990 - 004

V. RECORDS

PAGE 32

The prinlary records which were :maintained for the dec1ad progranl

consisted of the following:

RMDF1. In-Out Log - for fuel assemblies

Z. In-Out Log - for dec1ad fuel

AIEL

1. Laboratory Manufacturing Production Order (LMPO)

tailored after the MFa (Ref: QAOP 5.1) which detailed

the step-by-step operational procedures and sequencing.

2. In Process Status Log - maintained the in-process

traceability of the fuel.

3. Shipping Canister Loading Record

4. Laboratory Notebooks - used to collect all process

and physical inspection data, along with deviations

from operational procedures.

NMM

The Nuclear Material Management records are explained

in detail in NMP-704-990-001 Rev. A, IISRE Fuel Dec1adding

NMM Planr,.


Atomics International NO l'-l'704-FDR-990-004

PAGE. 33

VI. PROGRAM DOCUMENTS

A summary of the supporting program documents is presented in

Table III.


Documents I Revision

PP-704-990-002 Rev A

QFP-704-990-00 1 Rev ANMP-704- 990-00 1 Rev ATI-704- 990 -0 18 Rev ANSA-704-990-001 Rev BN704-NSA-990-002 N/COP-OO 1-140-00 1 NlcRPA-704-990-00l Rev C/4

TP-704- 990-00 1 N/CTP- 704- 990 - 002 N/CN704- ER- 990 - 00 2 N/CTR-704- 990-00 1 N/CN704- TR-990-002. N/CN704-ACR- 990-009 N/CN704-DWP-990-0l3 N/CNK396-00002 N/c

N704-0P- 990-002 Rev A

Drawings

EX-N704000025 Rev AEX-N704000065 N/CEX-N704000067 N/CEX-N704000068 N/CEX-N704000069 N/CEX-N704000070 N/C

TABLE III

SRE FUEL DECLADDING PROGRAM(SUPPORTING DOCUMENTS)

Title

Decontamination and Disposition of Facilities Program PlanaRE Fuel Decladding Quality p. s surance Functional PlanSRE Decontamination Nuclear Materials Management PlanCriticality Study - SRE Cores I and II FuelsSRE Fuel Decladding Nuclear Safety AnalysisSRE Core II Fuel Decladding Nuclear Safety AnalysisRadiation Safety Procedures for Atomics International Hot LaboratoryEngineering Release Plan of Action for the Decontamination· and

Disposition of Facilities ProgramNaK Distillation Test PlanSRE Fuel Decladding-Closure Weld Development Test PlanSelection of NaK Removal Process for Damaged SRE FuelSRE Fuel Decladding - Closure Weld Development Test ReportSRE Fuel, Acid, and Water Bath Reaction Test ReportActivity Requirement for Loading and Shipping SRE FuelDetailed Working Procedure for Loading and Shipping SRE Declad FuelTiedown Specification, Truck Shipment, TREAT and

Transfer Casks, SRE FuelSRE Fuel Transfer With Babcock Cask

SRE - Savannah River Core #Experimental Shipping CanSRE - Savannah River Core II Shipping CanSRE - Savannah River ~azy Susan ContainerGuide Plate - Lazy Susan ContainerBottom Plate - Lazy Susan ContainerEye Support, Tubing, Lazy Susan Container

~

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APPENDIX A

DISPOSITION OF CONTENTS FROM

16 UNIDENTIFIED RMDF STORAGE CONTAINERS


Atomics Intemationa. NO ....~704-FDR-990-004

PAGE A-I

INTRODUCTION

Fuel from both Core I and Core II of the Sodium. Reactor ExperiInent

has been stored in the Radioactive Materials Disposal Facility (RMDF) at

Ato:m.ics International. As part of the Decontam.ination and Disposition of

Facilities (D&D) Program., AI was funded to declad all the stored fuel

from SRE Cores I and II (including some SRE experiInental fuel), remove

the NaK bond, and repackage the fuel for shipment to Savannah River for

reprocessing

From. Nuclear Materials Management (NMM) records, it appeared

that the Core I fuel was packaged in 23 storage containers at the RMDF.

During the initial Core I phase of the decladding task, discrepancies were

encountered between the Source and Special (55) Nuclear Material transfer

records and the actual contents removed from the storage containers.

This situation led to a visual exam.ination of all 280 storage holes in Vault

I of the RMDF. As a re suIt of the exam.ination, sixteen of the hole s

were found to contain storage cans that did not have 55 material transfer

vouchers or other records to identify the contents.

A. APPROACH

AI's Nuclear Material Managem.ent was contacted and detailed search

into old records revealed that eight (8) of the RMDF storage holes in Vault

I had contained unidentified 55 material, which was reported as disposed

of by burial as of November 4, 1964. This discrepancy led to the con

clusion that any or all of the sixteen unidentified storage cans could con

tain special nuclear material. A program. was underta.ken to transfer the

unidentified storage container s to the AI Hot Laboratory Facility (AIHL)

for exa:mination of the contents. All of the cans were found to contain fuel

material. All of the fuel was examined for identifying numbers. When

numbers were found on identifiable fuel rods, slugs, or elements, the

NMM records were sea.rched to determine the quantity and composition of



PAGE

N704-FDR-990-004

A-2

the material. Table A-I presents the contents and disposition of the ma

terials contained in the sixteen unidentified containers. Seventeen line

items are shown in the table, since can U-3 contained a "hollow" experi

mental element which had SS material transfer vouchers for content: how

ever the position in the RMDF storage vault had been incorrectly recorded.

B. DISPOSITION

All fuel tba t was visually identified as SRE form material was dec1ad,

cleaned, and the NMM records searched in an attempt to identify the ma

terial. Fuel material that was positively identified as low enriched urani

um metal or uranium-molybdenum was weighed and repackaged for re

processing by Savannah River along with the other SRE Core I fuel. Fuel

material positively identified as high enriched uranium-thorium Core II

fuel, which Savannah River could also reprocess, was weighed and re

turned to the RMDF for packaging with SRE Core II fuel. Material which

was identified as UZr was weighed and returned to the RMDF for disposal.

SRE form material which could not be positively identified was also weighed

and returned to the RMDF for disposal. The three storage cans (U -14,

U-16 and U-I7) which contained materials experiInents not related to the

SRE were returned to the RMDF for disposal in the original storage con

tainers.

C. ACCOUNTABLE FUEL QUANTITIES

SRE-form fuel containing a total of 10,395.92 grams U235 was ac

counted for as a result of this inspection and repackaging task. This total

is composed of 6,921.34 grams U235

in identified unalloyed uranium slugs

and 704.94 grams of U235

in identified U-Mo slugs for recovery with the

scheduled Core I fuel reprocessing, and 628.90 grams of U235 in enriched

thorium-uranium fuel for recovery with the Core II SRE fuel; for a total of235 2358255.18 grams of recovered U . The balance of the SRE-form U ac-

counted for is 2,140.74 grams of unidentified uranium metal, thorium.

uranium, and uranium.-mo1ybdenum .



PAGE

N704-FDR-990-004

A-3

TABLE A-I

UNIDENTIFIED STORAGE CANISTER CONTENTS

Can Material OuantityType

U-I Unidentified 7.5 slugsSRE form equivalent

U-Z U 60 slugs

U-3 U-Hollow iz cylinders

U-4 U 60 slugs

U-Zr 1.4 slugs

U-5 Unidentified I slug very badSRE form 1. qt fines

U-6 U 3 slugs

Disposilion

Disintegrated upon examination

SU-I2.-I, U metal, repackaged for recovery.

Material originallydropped from inventoryan NOL 1.07

SU-Z-3

SU .3-1., single rod hollow element, located in differentstorage slot than indicated by records. .

SU·I'-l, material originally believed to have beendisposed of as waste under NOL 2.07

Remainder of mining portion of element 7152.0-035identified under NMM ticket No. 03345 I (hole ZO).

I slug labeled 6Z-J, indicating that the material m;,ghtbe from rod 583 and consist of U 1.8'/0 Me enrichedZ.778.

Rod 1.05

Rod 1.1.6

Rod 591.

Rod 541

Rod 570

Rod 551

Held atHotLaboratory for Core II repack;Lging.

Rod 584

Rod 603

Rod 544

Rod 556

Rod 557

Rod 534

Rod 535

Rod 53Z SU -1.-5

SU-1-38 (5 rods received and identified)

6 rods from SU-l-ZO

Disposal "No ill" CanOl.

Recovery AI-19

Recovery-58 slugs AI-161. slugs AI-17

Disposal "UZr" Can (I)

DispollalllNo !D" Can

Recovery Al_16(Z}

1 slug Recovery AI-171. slugs DisposaltlNo ID" Can

Disposal "No ID" Can

Disposal fiNo ID" Can

Recovery - AI-IS

Recovery - AI-18

Recovery - AI-18

Recovery - AI-18

Recovery - AI-18

Di.posal-"UZr ll Can

Recovery

Recovery - AI-18

Recovery - AI-18

Recovery - Al-18

Disposal-llUZr" Can

Diapoaal-I'UZr" Can

Recovery-"SNAP" Can

Recovery.IISNApll Can

Recovsry AI-17

Recovery-36 slugs AI-17

Disposal .. Jo6 It}1+gea*I-18Rec:overylnSNAp 11 Can(3)

1-1. in. pc

16 slugs and1-4 in. pc

3 slugs

3 slugs

13-1 in. sluga

4 slugs

6 slugs

I slug

8-1111. equivslugs

11. slugs

11. slugs

11. slugs

72,-1 in. pcs

11. equiv slugs

11. equiv slugs

lZ equiv slugs

60 slugs

72, slugs

11..5 equiv. slugs4 equiv slugs

UnidentifiedSRE form

U-7 U

U-8 U

U-9 Th-U

U-IO UnidentifiedSRE form

U·11 U-Mo

U-Mo

U-Mo

U-Zr

U-Zr

TH-U

Th-U

1]-12 1]

U

U

1]-Mo

U-Mo

U-Zr

Th-U

U.13 U 6 alugsS slugs

11-3/4 equivsluga

Recovery - AI-17Recovery - Al-IS

Disposal-fiNo ID" Ca.n

Not SRE fuel. By records NMM was

U·14 U-IO Mo Net wt UI'Ui

Ul< Disposal(4) SU-9 ) authorized for dispoaal years ago.49&4 gm 4468 gm .4 n:rg;n Material originally dropped from

UC 539 514 10.01. 51. Disposa1(4) NAA 81-3 inventory NOL 33A. ERDA-SAN hasauthorized disposal as w"ste.

U-15 U 8 slugs 7-Recovery - AI-17 Slug E-35?

)I-Disposal.uNo ron

Material originally droppedCanfrom inventory as NOL 33A.

U-Mo I-liD. slug • RecoveryAI-18

.!:!!! .Yo %Ux ~

U-16 UC 757 718 10.01. n NAA-Sl-I

I Not SRE fuel. Material originally111. 107 25.603 1.7 Disposal(4) NAA.74-2 dropped from inventory as NOL 33A.

41.1. 402 9.95 40 A!-3-9 ERDA-SAN has authorized disposal as) wa.te.

.!:!!! 1& !! 'foUl< ~ Not SRE fuel• MaterialU-l7 l)C 934 95.60 415 7.000 Z9 M-"-' ] originally dropped from inven-

345 9.355 Dispoaal(41 tory as NOL-l393 87.70 31. OMRE 4-3

ERDA-SAN has authorized dis-756 98.82 664 9.490 P OMRE 4-5 and 4-3 po sa! aa .waste.

(1) 11 .... _11 Can denotes ID given to storage container pending disposal of contents as waste.(1.) AI-XX denotes serial number of AI shipping canister cantainM1g repackaged fuel for Savannah River reprocessing.(3) Retu:ned to RMDF for processing and repackaging with SRE Care II fuel.(4) Returned to RMDF in storage container pending disposal as w;Late.



PAGE

N704-FDR-990-004

A-4

Additionally, several non-SRE identifiable materialexperim.ents were

found, containing 602.0 grams of U235, per identifiable records. The un

identified SRE-form fuel and the non-SRE identifiable materials total

2742.74 grams of U235. This material experim.ent fuel was designated

for disposal by land burial. The details of this "waste" fuel is contained

in Table A-2.

The grand total weight of U235 accounted for as a result of this task

was 10,997.92, of which 8255.18 grams was recovered and 2742.74 grams

was disposed of by land burial. The status of all fuel material at the

end of the repackaging operations is shown in Table A-3.


Atomics Internationa. NO J,\f704-FDR-990-004

PAGE. A-5

TABLE A-2

FUEL WASTE FROM 16 UNIDENTIFIED CANISTERS

Fuel Form Uranium. U-235(gm) (gm)

U metal fragments, fines, etc 44,203.87 1,227.98(Unidentified SRE-form)

U-Zr 31,921.54 886.78

U-02 (OMRE) 1,009 95

U-C (NAA 81-3) 514 52

U-C (NAA 81-1) 718 72

U-C (NAA 74-2) 107 27

U-C (AI-3-9) 402 40

U-C (AI-24-1) 415 29

U-Th 27.89 25.98

U-Mo 4,468

Total 83,786.3 2,742.74


•

TABLE A-3

SUMMARY OF CURRENT STATUS(Sheet 1 of 2)

»,S'3o'en

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Repackaged Net Wt U U235Container (grams) (%) (0/0)

U U CommentsIdentity

x

AI-16 93491.49 100 2.778 2597.19 93491.49 118 slugs, U-metal, all from the 16 cans; 60slugs from U-2 (5 intact rods), 58 slugs fromU-4 (5 intact rods)

AI-17 92049.04 100 2.778 2557.12 92049.04 112 slugs, U-metal, all from the 16 cans;2 slugs from U-4, 1 slug from U-6, 60 slugsfrom U-7 (5 rods), 36 slugs from U-8 (3 rods),6 slugs from U-13 and 7 slugs from U-15

AI-I8 89359.20 99.58 2.778 2471.97 88983.89 U-meta1 and U-Mo, all from the 16 cans; 36slugs from. U-8 (3 rods), 6 slugs from U-11U-Mo (damaged element), 13 I-in. pes U-Mofrom U-11, 36 slugs from. U-12, 72 I-in. slugsU-Mo from U-12, 12 slugs U-Mo from U-12,5 slugs U from U-13 and 1 I-in. slug U-Mofrom U-15

AI-19 68666.0 100 2.696 1851.23 68666.0 18 hollow U-metal experimental slugs fromU-3, material on RMDF inventory but placedin wrong storage location

* 1253.96 44231. 76 Material, alloy U content, or enrichment un-Hanford 44720.42 100 2.778.Burial known; contains all fines from the 16 cans

(6267 grams), 7.5 slugs from U-1, 1 sluglabeled 62J, 2 slugs and 1 2-in. pc from. U-6,12.5 equiv slugs from. U-8, 12 slugs, and 5 pes(4 6-in. pes and 1 4-in. pc) from U-10, I slug(E-35?) from. U-15, and 11-3/4 equiv slugsfrom. U-13; placed in "NO ID" can and returnedto RMDF

---_.~

*Returned to AIHL from RMDF, repackaged into 6Mcfrums, shielded with soil, and shipped to the licensedland burial site at Hanford, Washington; buried in January 1976.Document Provided and Located on:


1 • "" .,.' ,.,

TABLE A-3

SUMMARY OF CURRENT STATUS(Sheet 2 of 2)

Repackaged Net Wt U U235Container (grams) (lifo) <%)

Ux U CommentsIdentity

Hanford:(c 32573.01 98 2.778 886.78 31921. 54 46 slugs, U-Zr: 24 slugs from U-4; 4 slugsBurial (Rod 556) and 6 slugs (Rod 557) froIn U-ll;

12 equiv slugs (Rod 550) fro In U-12; placedin "U_ Zr" can and returned to RMDF

AI-55 6767.71 5.4 93.13 340.34 365.45 13-1/ 2 slugs, Th- U; 4 equiv slugs (Rod 532)fro In U-9; 9-1/2 equiv slugs (Rods 534 and 535)from U-11; became part of contents in AI- 55,thorium - 5.40/0 uranium

AI-50 5889.84 5.4 93.12 288.56 318.05 12 slugs (Rod 529) froIn U-12; became part ofcontents in AI- 50, thorium - 5.4% uranium

* 602 7633Hanford Non-SRE materials experiments, returned toBurial RMDF in original storage containers, U-14,

U- 16, and U-17

*Returned to AlHL from RMDF, repackaged into 6M drums, shielded with soil, and shipped to the licensedland burial site at Hanford, Washington; buried in January 1976.

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